Responds to IE Info Notices 85-42 & 85-81 in Response to Joint Intervenors Appeal of ASLB Ruling in Favor of Applicant on Contention IV Re Use of Tlds.Svc List,Info Notices & Board Notification 85-083 EnclML20136J072 |
Person / Time |
---|
Site: |
Harris ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
---|
Issue date: |
11/20/1985 |
---|
From: |
Oneill J CAROLINA POWER & LIGHT CO., NORTH CAROLINA MUNICIPAL POWER AGENCIES, SHAW, PITTMAN, POTTS & TROWBRIDGE |
---|
To: |
Gotchy R, Moore T, Wilber H NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP) |
---|
References |
---|
CON-#485-285 IEIN-85-042, IEIN-85-081, IEIN-85-42, IEIN-85-81, OL, NUDOCS 8511250273 |
Download: ML20136J072 (16) |
|
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML18009A5741990-06-13013 June 1990 Provides Progress Rept of Arbitration Between CP&L & North Carolina Eastern Municipal Power Agency.Arbitration Shows Allegations Made in Power Agency Complaint as Lacking in Merit & Requests Dismissal of Complaint ML18009A5731990-06-12012 June 1990 Notifies That Arbitrator Issued Award in Proceeding & Advises of Eastern Municipal Power Agency Withdrawal of Request for Initiation of Informal Complaint Procedures Re Antitrust License Conditions Contained in License NPF-63 ML18022A7871990-02-23023 February 1990 Submits Info in Response to 900122 Request Re Initiation of Informal Complaint Procedures Per Section 5.3.2 of NUREG-0970.Util Conduct Violates Commmitment 4 in Antitrust License Conditions.Discovery Procedures Completed ML18005B0101989-08-0404 August 1989 Requests That Commission Dismiss North Carolina Eastern Municipal Power Agency Complaint Re CP&L Violation of Antitrust Conditions on Basis That Power Agency Has Pursued Claim in Multiple Forums & Reasons in CP&L 890615 Ltr ML18005B0131989-08-0303 August 1989 Requests Commencement of Informal Complaint Procedures Per Section 5.3.2 of NUREG-0970 for Listed Reasons ML18005A9531989-06-22022 June 1989 Presents Licensee Request for Commencement of Informal Complaint Procedures Under Section 5.3.2 of NUREG-0970. Recommends That Util Request Be Denied & Parties Have Opportunity to Meet W/Commission to Discuss Util Complaint ML18005A9321989-05-18018 May 1989 Requests Commencement of Informal Complaint Procedures Under Section 5.3.2 of NUREG-0970.Util Requests Notification of All Meetings Betweeen NRC & Complaintant ML18022A7201989-05-0505 May 1989 Requests Commencement of Informal Complaint Procedures Per Section 5.3.2 of NUREG-0970.Related Info Encl ML20215K9211986-10-0808 October 1986 FOIA Request for Documents Re Investigation of Safety Concerns Raised by Jj Mcweeney Re Facility ML18004B5811986-10-0707 October 1986 Forwards Certificate N-112 to Nelia Policy 1 & Certificate M-112 to Maelu Policy M-112 ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20206U8651986-07-0808 July 1986 Forwards Chatham County Board of Commissioners Resolution Endorsing Emergency Response Plan on 860707.Resolution Suppls Applicant Response to Intervenors Request to Continue Stay Indefinitely.Svc List Encl ML20206J2531986-06-24024 June 1986 Alerts Commission That Applicant Considers Coalition for Alternatives to Shearon Harris 860609 Petition for Leave Before Aslab & That Applicant Filed Response to Petition W/Aslab.Svc List Encl ML20198L5871986-05-29029 May 1986 Forwards Board of Commissioners of Chatham County 860527 Resolution Rescinding Prior Approval of Emergency Response Plan Pending Further Review of Unresolved Issues.Svc List Encl.Related Correspondence ML20137Z5791986-03-11011 March 1986 Requests That Gf Trowbridge Be Replaced as Addressee for NRC Correspondence in Accordance W/Listed Client Facility & Designated Addressee ML20141N2221986-02-28028 February 1986 Forwards Us Court of Appeals 810929 Per Curiam Order, Dismissing Util Petition for Review of Rule on Emergency Planning.Applicants May Wish to Discuss Order at 860304-05 Hearings.Svc List Encl.Related Correspondence ML20137N0721986-01-23023 January 1986 Informs That Author Will Present Argument on Behalf of Applicant at 860205 Oral Argument on Intervenor Appeal from 850820 Partial Initial Decision on Safety Contentions. Svc List Encl ML20137J0111986-01-13013 January 1986 Forwards Listed Documents Re Eddleman Contention EPX-8 Expounding on & Modifying Applicant 851220 Response to Eddleman Interrogatories.Motion for Summary Disposition of EPX-2 Being Filed Separately ML20136J4731986-01-0808 January 1986 Completes 860103 Partial Response to 851226 Order for Info Re Intensity & Duration of siren-produced Levels within Plant Emergency Planning Zone.Certificate of Svc Encl. Related Correspondence ML20141F7601986-01-0303 January 1986 Forwards Thunderbolt Siren Directivity Pattern Dbc at 100 Ft,650 Hz, Used in Preparation of Testimony on Eddleman Contention 57-C-3,in Response to ASLB 851226 Order. Svc List Encl.Related Correspondence ML20138B3781985-12-0909 December 1985 Forwards Applicant Proposed Findings of Fact & Conclusions of Law on Eddleman 57-C-3 (Night Time Notification) Re Collective OL for Facility ML20137Q1261985-12-0202 December 1985 Responds to ASLB Re Generic Safety Problems Involving Emergency Notification of Residents in Plume Zones.Ltr Based Exclusively on Evidentiary Record & Departs from NRC Process.Svc List Encl ML20136J0721985-11-20020 November 1985 Responds to IE Info Notices 85-42 & 85-81 in Response to Joint Intervenors Appeal of ASLB Ruling in Favor of Applicant on Contention IV Re Use of Tlds.Svc List,Info Notices & Board Notification 85-083 Encl ML20205G5301985-11-0808 November 1985 Confirms That Util Provided Exhibit 48 (EPA-600/1-77-010) & Exhibit 49 (Siren Map) Provided to Court Reporter. Documents Also Provided to ASLB & Other Parties Per Applicant .Svc List Encl ML20205G8371985-11-0707 November 1985 Forwards Technical Svc Lab Presenting Results of Eddy Current Exam of Sample of Steam Generator Tubes & Replacement Pages 19-22 for Applicant Testimony of HR Banks & Others.W/Certificate of Svc.Related Correspondence ML20205G5431985-11-0101 November 1985 Requests Amend to to Facilitate Planning for Hearing on Conservation Council of North Carolina Contention WB-3 Resuming 851112.Dupont Will Be Applicant First Witness. Svc List Encl.Related Correspondence ML20133J1741985-10-16016 October 1985 Forwards Form 8-K,dtd 850924,filed W/Securities & Exchange Commission by Util.Svc List Encl.Related Correspondence ML20132B2351985-09-23023 September 1985 Forwards Direct Testimony Applicant Will Present at 850930 Hearing on Drug Use Contention,Per ASLB 850918 Order.List of Testimony & Exhibits Encl.Certificate of Svc Encl.Related Correspondence ML20134E8571985-08-16016 August 1985 Advises That Author Will Present Argument on Behalf of Applicant on 850828 Re Intervenor Appeal from ASLB 850220 Partial Initial Decision on Environ Contentions.Svc List Encl ML20126K8561985-07-26026 July 1985 Discusses Util Response to W Eddleman 850619 Request That Documents Be Made Part of Record in Proceeding,Per Board 850715 Order.Util Application for Withholding Untimely by Terms of 10CFR2.790.Related Correspondence ML20127B5231985-06-19019 June 1985 Requests That Documents Identified in Discovery on Contention 41-G Re Harassment Be Made Part of Record in Proceeding for Possible Consideration on Appeal.Copy of Documents Also Requested.Related Correspondence ML20126A0681985-06-10010 June 1985 Forwards Testimony of Jf Myers & Ds Mileti on Epj Contention 4(b) Re Role Strain in Adult School Bus Drivers. Applicants Do Not Plan to Offer Any Exhibits in Response to Contention.Certificate of Svc Encl ML20127M6261985-05-20020 May 1985 Forwards 840830 Final Rept of Facility Qa/Qc Const Inspector Review Panel & Four Documents Re Allegation of Harassment by Qa/Qc Inspector in Support of ASLB Denial of Eddleman 850507 Motion.W/O Encl.Svc List Encl.Related Correspondence ML20117J1501985-05-13013 May 1985 Informs That W Eddleman Will Not Be Filing Opposition to Motion for Summary Disposition of Eddleman 213.Eddleman 213 & EPT-2,as Discussed in ,Are Now Ripe for Summary Disposition.Svc List Encl.Related Correspondence ML20117H4181985-05-0909 May 1985 Notifies That Chapel Hill Anti-Nuclear Group Effort Will Not File Response to Jf Myers 850425 Supplemental Affidavit Re EPJ-2.Staff/FEMA Position on Affidavit Unchanged.Notice Authorized by Parties.Svc List Encl.Related Correspondence ML20116H5841985-04-29029 April 1985 Notifies of Mod to Evidence Presented in Response to Eddleman Contention 41 Re Pipe Hanger Welding.Verification of Pipe Hanger Design Compliance Will Be Performed by Craft Supervisors ML20116C9951985-04-25025 April 1985 Forwards Supplemental Affidavit of Jf Myers Re Recent Change to Provisions for Official Transportation Assistance for Persons in Emergency Planning Zone.Related Correspondence ML20115G4981985-04-18018 April 1985 Requests That ASLB Defer Summary Deposition Ruling on EPJ-2 Pending Submittal of Amended Affidavit from State of Nc Explaining Policy Decision Re Pickup Routes for Areas of Harris Plume Emergency Planning Zone.Svc List Encl ML20112C7801985-03-18018 March 1985 Amends Concluding Paragraph of Re Status of Pending Emergency Planning Summary Disposition Motions. Eddleman Response to Applicant Summary Disposition Motions on Contentions 30,57-C-10,213-a & 215 Received.W/Svc List ML20112B6321985-03-15015 March 1985 Discusses ASLB 850227 Memorandum & Order Re Emergency Planning Summary Disposition Motions.Applicants Received No Other Intervenor Responses or Requests for Extension Re Remaining Motions.Related Correspondence ML20099J3701985-03-14014 March 1985 Discusses NRC Re Eddleman 850301 Motion to Compel Discovery of NRC Staff.No Provisions of Code of Prof Responsibility or Commission Rule of Practice Relieve NRC of Obligation to Respond by Pleading.Related Correspondence ML20134G0611985-03-12012 March 1985 FOIA Request for All Records Re C Van Vo (Also Known as Vv Davis) 841006 Affidavit,Concerns Expressed in Affidavit & NRC Response to Concerns,Including Documents About Subjs Forming Basis for Insp Repts 50-400/84-43 & 50-400/84-45 ML20101S9791985-02-0101 February 1985 Forwards Application for Issuance of Subpoena Duces Tecum to C Van Vo,Proposed Subpoena & Notice of Deposition of C Van Vo.Applicant Will Undertake Svc of Subpoena After Execution.Related Correspondence ML20104A3831985-01-29029 January 1985 Reaffirms Commitment to Include All Map Info Required by NUREG-0654 in Annex 1,Rev 1 to Emergency Response Plan,Per Terms of Rejection of Eddleman Contentions 250 & 251.Svc List Encl ML20112J8391985-01-14014 January 1985 Forwards Motions Addressing 12 Contentions.Summary Disposition of All Outstanding Admitted Emergency Preparedness Contentions Except Wilson Contention 11 Sought by Applicants ML20112D9381985-01-10010 January 1985 Forwards Errata & Amends to 841221 Applicant Proposed Findings of Fact & Conclusions of Law Re Safety Matters to Correct Typos.Svc List Encl ML20101P0721985-01-0303 January 1985 Forwards Joint Motion for Approval of Settlement of Eddleman 227-S Submitted Jointly by Applicants,Eddleman,Nrc & Fema. Proposed Order Approving Settlement of Eddleman 227-S Encl ML20101E9421984-12-21021 December 1984 Forwards Applicant Proposed Findings of Fact & Conclusions of Law on Safety Matters.Certificate of Svc Encl ML20100B3231984-12-0303 December 1984 Forwards NRC Issued SERs on Reliability of Tdi Diesel Generators,Per Applicant Oral Motion Re Two Deferred Eddleman Contentions on Diesel Generators & ASLB Request for Suppl.Svc List Encl.Related Correspondence ML20094B1321984-11-0505 November 1984 Forwards 841105 Corrections to Jf Nevill,Ag Fuller, Dr Timberlake & Kv Hate 840809 Testimony Re Eddleman Contention 41 (Pipe Hanger Welding).Related Correspondence 1990-06-13
[Table view] |
Text
. _.
' 2-@,
s SHAW, PITTMAN, PoTTs & TROWBRIDGE a .am,N.msMi. #NcLuo.bMgSeI60NAL COR.oma, sons U Wi t.
1800 M STREET N. W.
WASHINGTON D. C. 20036
-7 em.e.
N
. j. a==.=m.. = ~~su.~. . -
- c. c .t gc. 85m ilo.W..F.. A11 m=v.ws'~:01 rsp we-phi ,gg. .o.,g a 7 g, . c . . . . . . sm v.=~a p '
neda. ms
-N
. lng ..
~
=
- b. g @
. ..i..r,. ..
, - g. . c.L; pnac3 ' F y" o<,m ..< c.r.s h,,,, # .
[E. s. f..-).,$..,.,',,..
e.. .gr. ='~.d...c. .eN -
bit'ol'E~ FEE""'"'" BRMCH n
,'gE(E$g..,g==aN No~7@.,['u"."^~
I'$$-M[th.5?c eg. w.'*'~ ' - = <m -.-' - - - > :.~s e,,, m r et, auru e m.wr gu4,:,g.sw P..
ww. eru s.pw ..ye -s=.t.. n g. -G~irge~ c - = ~'- m.cn.~.w.v
- ~, r .s N .-
i&' =.w ~: xq=N
.N.y .. %,,.c
. , - o y.ua: c..,1
=a. a c-
. . , ,c w co . .. ...N.. o,,.c . . m ..
mxr=. e'c-*.o m o mi. o,. *~.. ...
i, o '2 ~.g.gd
.. . c.
N-.n e.
- r as ..
. c .. ~. s-b~.rp;ggy o I.a n e'.aN. viao Nia arion N ~.' lW * .s- ;
tsp ,wymt
. u.s ,, '..e. k=m% d van.u-1,asse...,~ -
n=" - -
~ mm.u =5.c r
po m:x.s.: r, w .ne. . ".s nu.r...we cu-m.s a u m xmN,
- =~-
c amie.w.:.. ~. . pro =,.b.. "a>--' n-h:w.u.&.sc,,,.
= =.v = .tre Jc.ee.S .. -AMLIN, C.
gL.LI.a D
SA A. R m.DO.A,r
- e. "
w3.: m n~
J.FFM.YR.SN,.c0 R*
u SUSAN C. LONGS,.. m...e FR.D ORASN.R sect asesevene aos sc.
JoHNF.O.AL,e
- amauevse see wi.oisem RSC ARO .. ..A Y me..R... CONN coWN..L November 20, 1985 202/822-1148 Thomas S. Moore, Esquire Dr. Reginald L'. Gotchy Chairman Atomic Safety and Licensing Atomic Safety and Licensing Appeal Board Appeal Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Mr. Howard A. Wilber Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In'the Matter of Carolina Power & Light Company and North Carolina Eastern Municipal Power Agency (Shearon Harris Nuclear Power Plant)
Docket No. 50-400 OL Administrative Judges Moore, Gotchy and Wilber:
The Joint Intervenors in this proceeding have appealed from the Licensing roard's decision ruling in favor of Appli-cants on Joint Contention IV, which concerns Applicants' use of thermoluminescent dosimeters ("TLDs"). The Appeal Board and the parties were notified, by letter of October 2, 1985, from the NRR Division of Licensing, that the Office of Inspection 0511250273 851120 PDR ADOCK 05000400 g PDR h $O).
T 1
SHAW, PITTMAN, PoTTs & TROWBRIDGE A PARTNER 3 Map INCLUDING PROFESSIONAL CORPORATIONS November 20, 1985 Page 2 and Enforcement had issued an information notice (IN 85-42) on an anomaly relating to TLDs manufactured by Panasonic, such as Applicants intend to use at the Harris facility (Attachment 1).
On October 17, 1985 the Office of Inspection and Enforcement issued an additional information notice (IN 85-81) concerning the Panasonic TLDs (Attachment 2). We are writing to inform the Appeal Board of Applicants' responses to those two notices.
IN 85-42 alerted licensees and applicants to the fact that loose phospor elements in some Panasonic TLD badges have re-sulted in erratically high readings. Although no specific ac-tion or written response was required by the information no-tice, Applicants undertook an internal investigation of the potential problem. The results of that internal investigation were set forth in a memorandum, a copy of which is attached hereto for the Appeal Board's information (Attachment 3). As the memorandum indicates, Carolina Power & Light company
("CP&L") has observed one instance of a loose phospor element, in a TLD used at the H.B. Robinson facility. This is the only case of a loose phospor that has been observed in the 30,000 Panasonic TLD badges used by CP&L. The problem can be detected during the periodic check of TLD badges or, as it was in the observed case, in an inspection performed for the purposes of investigating an abnormally high reading.
IN 85-81 notified licensees and applicants who use Panasonic TLDs of two additional potential sources of errone-ously high readings. In some cases anomalously high readings have been reported when the lead filters in badges became con-taminated with trace amounts of naturally occurring radioiso-
! topes. In another case, an unexpectedly high measurement was obtained upon reading the badge of an employee at CP&L's l
Brunswick facility who had been working on cleaning decayed ma-rine life out of the plant intake structure. Although no actu-al radiation exposure was expected or incurred in this environ-ment, the H 2 S gas given off by decaying marine life caused the TLD to regi5ter an abnormally high response.
On November 15, 1985 CP&L prepared a memorandum setting forth the results of its internal investigation of the two po-tential problems addressed in IN 85-81. A copy of the memoran-dum is attached hereto for the Appeal Board's information (At-tachment 4). Contaminated lead filters had been observed at CP&L and the affected badges had been removed from service. In the future, all new TLD badges will be screened for self-irradiation effects. With regard to the high response caused by H 2 S gas, CP&L instituted a system of sealing the TLD badge
)
SH Aw, PITTM AN, POTTs & TROWBRIDGE A PARTNERSHsP INCsuOtNG PeoF(SSCNAL CCRPORATONS November 20, 1985 l Page 3 l l
inside a gastight, impermeable container. This eliminated the !
effect of H 7 S on TLD badges. CP&L also has incorporated infor-mation about the problem caused by exposure to H S into its processing procedures and has issued a memorandud to employees at its three plants discussing the effectiveness of various protective coverings for the.TLD badges. No further instances of this anomaly have been observed.
Applicants believe that they have made an adequate re-sponse to the issues raised in the information notices and have taken appropriate measures to ensure that the erroneous readings do not occur again. Moreover, each of the detected anomalies has resulted in an erratically high TLD reading.
Therefore the potential sources of error have not and will not affect Applicants' ability to protect the health and safety of their personnel.
R pe .ful y suhkitte ,
Joh H. O'Neill, Jr. lr*5' l j
A Cou sel for Applicants v cc: Service List attached JHO:jb
-- g. ]
l
.,v e
DC L d:. i : l I U3NRC UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
'85 NOV 22 All:01 i BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD OF nL L u : uh W 00CKETING & SEPM--
In the Matter of BRANCH
)
)
CAROLINA POWER & LIGHT COMPANY ) Docket No. 50-400 OL and NORTH CAROLINA EASTERN )
MUNICIPAL POWER AGENCY )
)
(Shearon Harris Nuclear Power )
Plant) )
SERVICE LIST Thomas S. Moore, Esquire Charles A. Barth, Esquire Chairman _ Janice E. Moore, Esquire Atomic Safety and Licensing Office of Executive Legal Director Appeal Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commmission Washington, D.C. 20555 '
Washington, D.C. 20555 Docketing and Service Section Dr. Reginald L. Gotchy Office of the Secretary Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Appeal Board Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Daniel F. Read, President CHANGE Mr. Howard A. Wilber P.O. Box 2151 Atomic Safety and Licensing Raleigh, North Carolina 27602 Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 John D. Runkle, Esquire Conservation Council of James L. Kelley, Esquire North Carolina A om c Safety and Licensing Board Chapel Hill, North Carolina 27514 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 M. Travis Payne, Esquire Edelstein and Payne P.O. Box 12607 Atom c Saf ty and Licensing Board Raleigh, North Carolina 27605 i
U.S. Nuclear Regulatory Commission Washington, D.C. 20S55 Dr. Richard D. Wilson 729 Hunter Street Dr. James H. Carpenter Apex, North Carolina 27502 Atomic = Safety and Licensing Board
, U.S. Nuclear Regulatory Commission Washington, D.C. 20555 y e-, - - - - - - -
w , ,, wy v -wr,, y w---- w- w -+nwm w-%,
V t
5 I
Mr. Wells Eddleman 806 Parker Street Durham, NC 27701 Richard E. Jones, Esquire Vice President and Senior Counsel Carolina Power & Light Company P.O. Box 1551 Raleigh, North Carolina 27602 Dr. Linda W. Little Governor's Waste Management Board 513 Albemarle Building 325 North Salisbury Street Raleigh, North Carolina 27611 Bradley W. Jones, Esquire U.S. Nuclear Regulatory Commission Region II 101 Marrietta Street Atlanta, Georgia 30303 Mr. Robert P. Gruber Executive Director ,
Public Staff - NCUC P.O. Box 991 Raleigh, North Carolina 27602 Administrative Judge Harry Foreman Box 395 Mayo University of Minnesota Minneapolis, Minnesota 55455 H. A. Cole, Jr., Esquire Special Deputy Attorney General 200 New Bern Avenue Raleigh, North Carolina 27601
l ATTACHMENT 1 !
[ #
'o UNITED STATES E" 7. NUCLEAR REGULATORY COMMISSION h WASHINGTON. D. C. 20555 O E
\, .....##
00T 2 1985 Docket No.: 50-400 MEMORANDUM FOR: Atomic Safety and Licensing Appeal Board for Shearon Harris, Unit 1 (T. S. Moore, R. L. Gotchy, H. A. Wilber)
FROM: Thomas M. Novak, Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation
~
SUBJECT:
SHEARON HARRIS NUCLEAR POWER STATION - PANASONIC THERM 0 LUMINESCENT DOSIMETER (TLD)
(BOARD NOTIFICATION NO. 8S-083)
In accordance with NRC procedures for Board Notifications, the enclosed IE Information. Notice which describes an annomaly relating to a Panasonic TLD, -
is provided for your information. The panasonic TLD was one of the admitted contentions in the Shearon Harris licensing proceedings.
By copy of this memorandum the Atomic Safety and Licensing Board and the parties to the Shearon Harris proceeding are provided the same information.
Thomas M. Novak, Assistant Director
... for Licensing
. Division of Licensing Office of Nuclear Reactor Regulation--
Enclosure:
As stated cc: J. L. Kelly, ASLB G. O. Bright, ASLB J. H. Carpenter, ASLB EDO ACRS (10)
Parties to the Proceeding 8510020462
/
1 l
DISTRIBUTION LIST FOR BOARD NOTIFICATION Shearon Harris Nuclear Power Plant, Units 1&2 Docket Nos. 50-400/401 Atomic Safety and Licensing Appeal Board Atomic Safety and Licensing Board Panel Docketing and Service Section Document Management Branch Mr. Glenn 0. Bright Dr. James H. Carpenter H. A. Cole, Jr. , Esq.
Wells Eddleman Dr. Harry Foreman Mr. Robert P.,Gruber Bradley W. Jones, Esq.
Richard E: Jones, Esq.
James L. Kelley, Esq.
Dr. Linda W. Little Mr.LTravis Payne Spence W. Perry, Esq. -
Mr. Daniel F. Read Mr. Steven Rochlis Mr. John Runkle George F. Trowbridge, Esq.
Richard D. Wilson, M.D.
Mr. E. E. Utley M. David Gordon, Esq.
Thomas S. Erwin, Esq.
Resident Inspector / Harris NPS Charles D. Barham, Jr. , Esq.
Mr. George Jackson, Secretary Regionai Administrator, Region 11 s
Enclosure O'#
5 No.: 6835 IN 85-42 I -
UNITED STATES l NUCLEAR REGULATORY COMMISSION l OFFICE OF INSPECTION AND ENFORCEMENT I i WASHINGTON, D. C. 20555 !
May 29, 1985 IE INFORMATION NOTICE NO. 85-42: LOOSE PHOSPHOR IN PANASONIC 800 SERIES BADGE THERM 0 LUMINESCENT DOSIMETER (TLD) ELEMENTS i
Addressees:
All holders of a nuclear power plant operating license (OL) or a construction permit (CP). ,
Purpose:
! This information notice is provided to alert NRC licensees to a problem noted in some Panasonie 800 series TLD badges that has caused spurious high readings in one of the badges' TLD elements,. This information is intended to assist ,
lice,nsees in diagnosing any spurious readings with the Panasonic TLD system. ,
It is expected that recipients will review the information provided for appli- '
, cability, if appropriate, to their dosimetry programs. However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
~. -
l Description of Circumstances:
The Panasonic 800 series TLD badge contains a card that holds four TLD ele-ments. Each TLD element consists of a thin film of TL phosphor attached to a
- disk backing with a clear teflon bubble cover. During reading, the phosphor is heated by convarging infrared light on the backing. The luminescence froid the l
phosphor (which is proportional to the dose received) radiates through the teflon cover and is read with a photomultiplier tube.
Several Panasonic TLD users (including NRC's Region I) have identified badges
)
where crystals of the phosphor have detached themselves from the backing of the
, element -resulting in high erratic readings in that element. When viewed through a stereoscopic microscope, phosphor crystals can be observed sticking to the teflon cover (presumably.by electrostatic charge). In this position, the loose TL material is not in contact with the backing and does not get heated when the badge is read. These TL crystals remain at an elevated energy state and continue to accumulate dose. Apparently erratically high readings result when the loose crystals are shaken back onto the backing surface during a subsequent reading. They are then heated and luminescence proportional to the total doses received during several read cycles is produced. This process can cause the affected element to erroneously read as much as an order of magnitude higher than the other elements in the same card. Although the
- - - , , - - - . -- , - . , - - , - . - ,,._ ,.._. ,, ,_,.,- -.,.,, ,,,-.-.- , ,, ,,,_ _ + - c, ,nn,-,,-,- - - - , n. , , ---.
Attachment 1 s
IN 85-42 May 29, 1985 LIST OF RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to 85-41 Scheduling Of Pre-Licensing 5/24/85 All power reactor Emergency Preparedness facilities holding Exercises a CP 85-40 Deficiencies In Equipment 5/22/85 All power reactor Qualification Testing And facilities holding Certification Process an OL or CP 85-39 Auditability of Electrical 5/22/85 All power reactor Equipment Qualification facilities holding Records At Licensees' an OL or CP Facilities .
85-38 Loose Parts Obstruct Control 5/21/85 All PWR facilities
, Ro,d Drive Mechanism' d'esigned by B&W holding an OL or.CP 85-37 Chemical Cleaning Of Steam 5/14/85 All pressure water Generator At Milestone 2 reactor facilities holding an OL or CP 84-55 Seal Table Leaks At PWRs 5/14/85 All power reactor Sup. 1 -
facilities holdtng an OL or CP 85-20 Motor-Operated Valve Failures 5/14/85 All power reactor Sup. 1 '
Due To" Hammering Effect facilities holding an OL or CP ,,
85-36 Malfunction Of A Dry-Storage, 5/9/85 All licensees Panoramic, Gamma Exposure possessing gamma i Irradiator irradiators S4-52 Inadequate Material 5/8/85 All power reactor Sup. 1 Procurement Controls On facilities holding The Part Of Licensees And an OL or CP Vendors I
l l
OL = Operating License CP = Construction Permit
( IN 85-42 May 29, 1985 Page 2 of 2 frequency of occurrence is small (one licensee found only one problem badge in 30,000), there is evidence that the frequency increases substantially once the badges have been thro' ugh 100-200- read cycles.
Panasonic has a manufacturing quality control (QC) specification on the amount of loose phosphor in an element. However, physical shock and thermal cycles, experienced during badge use, appear to loosen additional material. Panasonic '
has stated that they have modified their QC program to provide a greater-physical challenge to the badge before they are screened. For those badges already in use, licensees can visually inspect any TLD elements suspected of l
having loose TL crystals. Panasonic has been exchanging badges identified as having excessive loose TL material.
No specific action or written response is required by tais information notice.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office.
l
]
wr Lf Jordan, Director .
l Divi on.of Emergency Preparedness -
an Engineering Response Office of Inspection and Enforcement
! Technical Contacts: R. L. Pedersen, IE (301) 492-2967 -
l J. E. Wigginton, IE (301) 492-9425 l
Attachment:
- List of Recently Issued IE Information Notices e
J
i SSINS No.: 6835 ATTACHMENT 2 IN 85-81 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT PUBLIC ?tCUMENT h October 17, 1985 15 BCT 22 A9:45 IEINFORMATIONN$QC%EkhEg8-81: PRDBLEMS RESULTING IN ERR 0NEOUSLY HIGH READING WITH PANASONIC 800 SERIES
- THERM 0 LUMINESCENT DOSIMETERS Addressees:
All nuclear power reactor facilities holding an operating license (0L) or a construction permit (CP) and certain materials and fuel cycle licensees who may use the subject thermoluminescent dosimeters (TLDs).
Purpose:
Information Notices IN 82-42 " Defects Observed in Panasonic Model 801 and 802 TLD's" and IN 85-42 " Loose Phosphor.in Panasonic 800 Series Badge TLD Elements" discussed two separate problems with Panasonic TLD's that resulted in erroneous exposure measurements with the badges.
This information notice is provided.to inform the licensees of two additional problems that have resulted in erroneously high readings with Panasonic 800-series TLDs. It is expected th't a licensees will review this information for applicability to their facilities and consider actions, if appropriate, to preclude a similar problem occurring at their facilities. However, suggestions contained in this information notice da not constitute NRC requirements; therefore, no specific action or wr.itten response is required.
Description of Circumstances:
- 1. Self-Irradiation From Contaminated Lead Filters:
Several Panasonic TLD users have recently experienced anomalously high readings. On investigation, it was determined that the lead filters in the badges were contaminated with trace amounts of naturally occurring radioisotopes. The lead filters (on both sides of the TLD elements) are used to compensate for the energy dependence of calcium sulfate phosphor.
The lead used for these filters appears to be contaminated with radium-226 daighters. Bismuth-210 is a major dose contributor. Low level radiation fram these contaminants contributed up to 15 mrem in 30 days to the TLD elements. During the initial investigation of the anomalous readings, several TLD badges were counted using a gamma spectroscopy system. This technique was unable to identify contaminated lead filters because of the low activity of gamma emitting contaminants. However, when lead filters were recounted using a thin-wi'ndow Geiger-Muller (GM) detector, they were found to be contaminated with beta emitting radioisotopes.
8510150025
IN 85-81 Il Octobir 17, 1985
- i l
Page 2 of 3 Panasonic TLD's can be screened for contaminated filters by placing several-
. in a low background thin-window GM counter. Licensees wishing to use this screening technique should select a counting time sufficien't to provide an o acceptable lower limit of detection.(5 pCi beta per gram of lead) for their system. Panasonic is currently negotiating the repl,acement.of badges on a case-by-case basis, i
- 2. Abnormal TLD Readings Caused by Hydrogen Sulfide (H25) Gas On May 6, 1985, an unexpectedly high reading was indicated during a routine TLD processing of a terminating contract worker leaving the Brunswick Steam Electric Plant. The worker had been employed to clean marine life out of the plants intake structure, an area where no radiation is expected. He was issued a TLD because access to the job site was through the plant's protected area. The worker's TLD (Panasonic Madel 00-802) indicated 13,500 and 457 millirem on elements 1 and 2, respectively (both lithium borate TLQ material), with 1.2 and 1.4 millirem indicated on elements 3 and 4, respectively (calciur' sulfate TLD material). On; investigation, the licensee has concluded that the abnormal TLD response was caused by exposure to H 2 S gas given off by the cer ying marine life in the intake structure. Extensive testing by the licen.,e indicates that exposure to H S2 causes gross over-response from lithium borate TLD material. Multiple' exposures to concentrations as low as 10 parts per million (ppm) over a 12-hour period caused responses that
.correspcnd to 250 millirem of radiation exposure. Indication as high as 4870 millirem were obtained from a 4-hour exposure to 114 ppm H 25-Several agents (such as chemical co'taminants, n ultraviolet light or extreme humidity) are known to cause abnormal TLD responses. Licensees may wish to provide appropriate means of protecting the TLD when exposure to these agents is lim 1y. However, licensees should ensure that protective coverings or containers uo not inhibit the TLDs ability to properly respond to actual radiation exposure.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office.
j r L Divisio o
A ~
n, Director
~
f Emergency Preparedness and En ineering Response Office of Inspection and Enforcement Technical :ontacts: RogerPedersen,IE,!
(301)492-9425 Jim Wiggintor !E i (301)492-496:
Attatnments: .ist of Recently Issued IE Information Notices
- a. ,
Attachment 1 1
IN 85-81 October 17, 1985 -
LIST OF RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to i
85-80 Timely Declaration Of An 10/15/85 All power reactor l
Emergency Class Implementa- facilities holding l
' tion Of An Emergency Plan, an OL or CP And Emergency Notifications 85-17 Possible Sticking Of ASCO 10/1/85 All power reactor Sup. 1 Solenoid Valves facilities holding an OL or CP q
85-79 Inadequate Communications 9/30/85 All power reactor Between Maintenance, facilities holding Operations, And Security: an OL or CP; research Personnel and nonpower reactor
- facilities; fuel fabrication and processing facilities 85-78 Event Notification 9/23/85 All power reactor facilities holding an OL or CP Possible Loss Of Emergency 9/20/85 All power reactor 85-77 Notification System Due To facilities holding Loss Of AC Power an OL or CP 85-76 Recent Water Hammer Events 9/19/85 All power reactor facilities holding an OL or CP 85-75 improperlyInstalledInstru- 8/30/85 All power reactor mentation, Inadequate Quality facilities holding Control And Inadequate Post- an OL or CP modification Testing 85-74 Station Battery Problems' , 8/29/85 All power reactor facilities holding an OL or CP Reliance On Water Level 8/26/85 All power reactor 84-70 facilities holding Sup. 1 Instrumentation With A Common Reference Leg an OL or CP OL = Operating License CP = Construction Permit
ATTACHMENT 3 Form 204 Carolina Power & Light Company h% ceca ~.'.::*:'r'.'C-- I company corresponcene. New Hill, North Carolina June 26,1985 File: 13510F Serial: NO-85-H945 MEMORANDUM TO: Mr. A. G. Cheatham, III Mr. J. R. Sipp Mr. R. M. Smith 2 ROM: B. H. Webster
SUBJECT:
Response to IE Information Notice 85-42, " Loose Phosphor in Panasonic 800 Series Badge Thermoluminescent Dosimeter (TLD) Elements" The attached IE Information Notice 85-42 describes a problem with loose phosphor in Panasonic TLD badges like those used at CP&L. Loose phosphor can cause erratic response and high readings for the affected elements.
Several months ago loose phosphor was found to be the cause of an abnormal TLD element reading in one area monitoring badge at H.B. Robinson.
'Ihis is the only documented case of loose phosphor which has been observed in 30,000 TLD badges at CP&L.
All TLD badges at CP&L are tested periodically for proper response. In addition, and tested.any badges which exhibit abnormal readings are inspected for damage Any occurrences of loose phosphor in TLD badges at CP&L will be identified service. through these means and the affected badges will be removed from The above constitutes an adequate response to IE Information Notice 85-
- 42. No further action in response to this notice is planned.
If you have any questions, please contact me.
e m ,. .
B . H. J.;.. . A SAB/vvf Attachment ec: Messrs. D. N. Allen D. L. Erickson R. T. Biggerstaff R. E. Helme C.S.Bohanan R. L. Mayton !
H. W. Bowles J. A. Padgett S. A. Browne / D. C. Stadler K. E. Engor A. R. Wallace
ATTACi1 MENT 4 Form 244 ,
, Caronna Power & Light Company comoany corr soono.nc, New Hill, North Carolina November 15,1985 File: 13510F Serial: NO-85-H1695 MEMORANDUM TO: Mr. A. G. Cheatham, IU Mr. J. R. Sipp-Mr. R. M. Smith FROM: B. H. Webster
SUBJECT:
Response to IE Information Notice 85-81,
" Problems Resulting in Erroneously High Reading with Panasonic 800 Series Thermoluminescent Dosimeters" The attached IE Information Ndee 85-81 discusses two problems that have affected readings for Panasonic TLD badges like those used at CP&L. Both of the problems have been observed at CP&L and actions have been taken as described below:
- 1. Self-Irradiation from Contaminated Lead Filters:
Contaminated lead filters have been observed in some environmental and personnel TLD badges used at CP&L. Self-Irradiation was first noted in the environmental badges because of the interference it caused in measuring very low doses.
Subsequently, the problem was recognized in some personnel badges which were being used for background control purposes. AH of the affected environmental badges have been removed from service and replacement badge holders have been received from Panasonic. All of the affected personnel badges have been identified and Panasonic has agreed 'to replace the holders on these badges. On personnel badges only Element 4 is affected by the contaminated filters. Elements 1 and 2, which are normally used for estimating shallow dose to the skin and deep dose to the whole body, respectively, are imaffected.
Element 3, which is not normally used, is also unaffected. In addition to replacing the contaminated badge holders, all new' batches of TLD badges received in the future will be screened for self-Irradiation effects.
4 I M:morandum . Novsmber 15,1985 I
- 2. Abnormal Readings Caused by Hydrogen Sulfide (H25) Gas:
Panasonie has performed tests to confirm that H 2S gas does cause abnormally high response on lithium borate TLD phosphor which is used in Elements 1 and 2 of the TLD badge.
Interference from H 52 een be avoided by sealing the TLD badge inside a gestight, impermeable container. This method has proven successful in eliminating the effect of H25 on TLD be%es at the Brunswick Plant. Information about the interference of H is has been incorporated into the TLD badge processing procedures along with the most recent information available about other possible. causes of abnormal readings. In addition, a memo was issued on June 24,1985, to the Radiation Control supervisors at the three nuclear plants which discussed the effectiveness of various protective coverings against H28 and provided advice concerning beta exposure in the event the TLD is enclosed inside a protective covering. No further problems with H 2S gas interference have been observed at any CP&L facility since the occurrence described in the notice.
We consider the above to constitute an adequate response to IE Information Notice 85-81.- No fnarther action in response to this notice is planned.
If you have any questions, please contact me.
Origins 1 Signed By B. H. WEBSTER SAB/are Attachment i ce: Messrs: D. N. Allen l E. T. Biggerstaff C. S. Bohanan ,
H. W. Bowles S. A. Browne /
J. M. Curley E. L Ensor B. E. Helme R. I. Mayton A. M. McCauley B. A. Meyer J. A. Padgett
.